NSUF 19-2895: Predict the mechanical behavior of irradiated cast stainless steels based on the microstructures and measured properties from nanoindentation
The work is planned to systemically characterize the neutron irradiated CF3 and CF8 cast stainless steels irradiated to 3 dpa at 310°C. The study is aimed to complete the study of irradiation effect on the microstructural evolution in the ferrite phase of cast stainless steels and to predict their mechanical behaviors. Both the transmission electron microscope and atom probe tomography will be used to study the irradiated induced nano-sized features including dislocation, phase separation and precipitates. The nanoindentation will be applied to obtain yield strength and Young’s modulus of ferrite and austenite phases, separately. The output from the execution of proposed study will provide a more systematic study at an atomic level on the neutron irradiation effects in the LWRs internal structural materials at LWRs relevant conditions, and will help to predict their mechanical behavior through finite element modeling (FEM) using the parameters obtained from microstructural characterization and nanoindentation. This proposed research will provide a fundamental understanding on the response of cast stainless steels during the designed 40 years reactor life, and more relevantly, predicting their mechanical property for the extended life of 60 years and beyond.
Additional Info
| Field | Value |
|---|---|
| Abstract | The work is planned to systemically characterize the neutron irradiated CF3 and CF8 cast stainless steels irradiated to 3 dpa at 310°C. The study is aimed to complete the study of irradiation effect on the microstructural evolution in the ferrite phase of cast stainless steels and to predict their mechanical behaviors. Both the transmission electron microscope and atom probe tomography will be used to study the irradiated induced nano-sized features including dislocation, phase separation and precipitates. The nanoindentation will be applied to obtain yield strength and Young’s modulus of ferrite and austenite phases, separately. The output from the execution of proposed study will provide a more systematic study at an atomic level on the neutron irradiation effects in the LWRs internal structural materials at LWRs relevant conditions, and will help to predict their mechanical behavior through finite element modeling (FEM) using the parameters obtained from microstructural characterization and nanoindentation. This proposed research will provide a fundamental understanding on the response of cast stainless steels during the designed 40 years reactor life, and more relevantly, predicting their mechanical property for the extended life of 60 years and beyond. |
| Award Announced Date | 2019-09-17T14:48:33.473 |
| Awarded Institution | Center for Advanced Energy Studies |
| Facility | Microscopy and Characterization Suite |
| Facility Tech Lead | Yaqiao Wu |
| Irradiation Facility | None |
| PI | Yu Lu |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 2895 |